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In-Situ Testing of Nuclear Waste Glasses in a Clay Laboratory - Results After Two Years Corrosion

Published online by Cambridge University Press:  21 February 2011

P. Van Iseghem ,
W. Timmermans  and
B. Neerdael
P. Van Iseghem
Affiliation:
Department Nuclear Chemistry and the Fuel Cycle, S.C.K./C.E.N., B-2400 Mol, Belgium
W. Timmermans
Affiliation:
Department Nuclear Chemistry and the Fuel Cycle, S.C.K./C.E.N., B-2400 Mol, Belgium
B. Neerdael
Affiliation:
Department Nuclear Chemistry and the Fuel Cycle, S.C.K./C.E.N., B-2400 Mol, Belgium
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Abstract

The first retrieval of an in-situ experiment on the interaction waste form - clay host in the underground laboratory under the Mol site has been finished successfully. The test consisted in a two years exposure of various candidate simulated waste glasses at 90°C to Boom clay. The retrieval was done by overcoring. The experimental data showed satisfactorily correspondence between in-situ and laboratory simulation tests both for mass loss and surface analytical data, supporting the validity of the in-situ test as it was performed. The thickness of waste form dissolved within two years varies between 40 and 325 μm (case of the high-level waste glasses), depending on the composition. Matrix dissolution is expected to be the major mechanism of interaction.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 176: Symposium U – Scientific Basis for Nuclear Waste Management XIII , 1989 , 283
Copyright
Copyright © Materials Research Society 1990

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References

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